International Conference on Non-Electric Applications of Nuclear Power: Seawater Desalination, Hydrogen Production and other Industrial Applications 16 – 19 April 2007, Oarai, Japan FEASIBILITY STUDY ON DEPLOYMENT OF FEASIBILITY STUDY ON DEPLOYMENT OF THE FIRST UNIT OF RUTA- -70 REACTOR IN 70 REACTOR IN THE FIRST UNIT OF RUTA OBNINSK: DISTRICT HEATING, OBNINSK: DISTRICT HEATING, TECHNOLOGICAL, AND MEDICAL TECHNOLOGICAL, AND MEDICAL APPLICATIONS APPLICATIONS Yu.S. Cherepnin, A.A. Romenkov, F.Ye. Yermoshin Research and Development Institute of Power Engineering, Moscow, Russia V.M. Poplavskiy, Yu.D. Baranaev, V.A. Sozonyuk State Scientific Center of the Russian Federation – Institute of Physics and Power Engineering, Obninsk, Russia
Contents The paper presents a feasibility study on deployment of the first-of-kind RUTA-70 heat supply facility in Obninsk and prospects of various nuclear medical and technological applications of the reactor: Introduction I. Major technical data and design features of the reactor II. Using low-grade thermal energy generated by the reactor for district heating III. Using the reactor as a neutron source to implement various nuclear technologies IV. Using the reactor for desalination of seawater Conclusions
Introduction (1) The current experience shows that there are no technical obstacles for the use of nuclear reactor heat both in domestic district heating systems and in industrial processes Domestic district heating has a long history and proven experience in practical operation of nuclear facilities of various types Nowadays, nuclear reactors in the world generate less than 1% of the heat used for district heating and in industrial processes while the share of nuclear power plants in electricity production worldwide being � 15%
Introduction (2) Increasing Interest in utilization of nuclear energy for district heating in resent years in Russia: - continuos increasing of domestic gas price - difficulties and/or very high cost of fossil fuel supply to some remotely isolated areas of the country - country-wide reform in the municipal sector Dedicated nuclear heating plant with pool-type reactor producing low potential heat RUTA – Thermal Reactor Unite with Atmospheric pressure
Introduction (3) R&D at various design stages are carried out for RUTA reactors with thermal power ranged from 10 to 70 MWt Practical implementation plan - construction of the fist demonstration nuclear heating plant with RUTA-70 in Obninsk on the site of the IPPE The FS was prepared by Rosatom Institutes NIKIET (General and Reactor Designer) AEP (Architect-Engineering) IPPE (Research Supervisor)
I. RUTA-70 reactor design RUTA-70 1 – riser shroud, 7500 2 – poll metallic liner 13 12 3 – core supporting plate with control rod lead tubes, 11 4 – reactor core 10 5 – plenum 6 – check valve 7 – secondary water inlet 8 – secondary water outlet, 1000 17250 9 – primary pump O3200 O2150 10 – primary HX 12050 9 1 5 6 7 8 11 – upper header 8750 12 – control rod drives 2 4 13 – isolation plate 3
I. RUTA-70 reactor design RUTA-70 reactor facility 1 – Core 2 – Primary heat exchanger 3 – Check valve 4 – Pump 5 – Primary circuit distributing header 6 – Primary circuit collecting header 7 – Secondary circuit supply pipeline 8 – Secondary circuit discharge pipeline 9 – SCS drives 10 – Upper plate
I. RUTA-70 reactor design Basic technical characteristics of RUTA-70 Maximum reactor thermal power (N nom ), MWt 70 Core dimensions (diameter/height), м 1,42/1,4 cermet Nuclear fuel type (0.6 UO 2 + 0.4 Al alloy) Fuel enrichment, % of 235 U 4.2 Fuel campaign, eff. days 2 332 Refueling interval at CF=0.7, years 3 Portion of refueled assemblies 1/3 Pool water volume, m 3 250 Primary coolant circulation mode - at (30 – 100)% N nom forced - at (0 – 30)% N nom natural Primary coolant - temperature (core inlet/outlet), о С 75 / 101 - pressure in core inlet, MPa 0,27 Intermediate HX temperature (inlet/outlet), о С 68 / 95 Pressure, MPa 0,39 Main HX temperature (inlet/outlet), о С 60 / 90 Pressure, MPa 0,95
I. RUTA-70 reactor design Generic advantages of the technology important for heating reactor: - Principal design simplicity resulting in low construction and operation cost - High level of safety based on design features, inherent safety characteristics, and reliance on natural laws and forces to provide reactor protection: - Atmospheric pressure of primary circuit (no pressurization) - High heat capacity of reactor pool water - Negative reactivity feedback - Low fuel temperature and low value of core power density (30- 40 MWt/m 3 ) - Core cooling in coolant natural circulation mode at normal operation (up to ≈ 30%N nom ) and under emergency conditions - Three circuit heat transmission arrangement with two pressure barriers (double pressure reversal): p 1 <p 2 <p 3
II. RUTA-70 use for district heating The key feature of pool-type reactors is low temperature of the system water It defines the following operation approach: - RUTA covers the base segment of the heat load - Non-nuclear heat source is used for peak load and as a backup
II. RUTA-70 use for district heating • In a district heating systems with the maximum required temperature exceeding the available level temperature, system water should be heated by peak water heaters. In this case the capacity factor of the nuclear power source can be 0.6 - 0.8 • In some cases RUTA can ensure full heat supply over the year. But capacity factor is very low (0.3 - 0.4). So, in these cases it is also preferable to use the RUTA facilities in the base segment of the heat load jointly with peak non-nuclear heat generators
III. RUTA - neutron source Taking into account interests of various scientific institutes located in Obninsk-city, important factor favouring the implementation of the RUTA project is provision for multi- purpose application of reactor: • production of a broad range of radioisotopes for medical and industrial purposes • neutron and transmutation doping of silicon monocrystals for the needs of microelectronics • creation of neutron beams for neutron therapy • irradiation of thin polymer films for production of track membranes • neutron activation analysis
III. RUTA - neutron source The following irradiation devices are feasible: • irradiation channels in the reflector: - 8 channels for production of radioisotopes - 2 channels for neutron and transmutation doping of silicon - 2 pneumatic rabbit system channels for neutron activation analysis • medical irradiation neutron beams: - 1 for fast-neutron therapy (FNT) - 1 for neutron-capture therapy (NCT) • channel for irradiation of the polymer film used to produce track membranes
III. RUTA - neutron source 1 - reactor vessel; 2 – cover; 3 – core; 4 – FNT channel; 5 – film irradiation devices; 6 – fresh film cartridge; 7 – irradiated film cartridge 8 – TV camera; 9 – silicon nuclear doping channel; 10 – power density monitoring sensor; 11– SCS cluster; 12 – IC channel; 13 – SCS drive area; 14 – drive area trunk; 15 – handling trolley; 16 – cooling pool; 17 – upper ceiling. Irradiation devices at the RUTA reactor
III. RUTA - neutron source Neutron fluxes at the core center and at locations of irradiation channels and devices for the beginning (b) and the end (e) of the RI, 10 13 /(cm 2 ⋅ s) First row of Graphite Silicon FNT NCT the reflector column for doping channel channel Energy of Central FA (radioisotope TM (layer in channel neutrons in production the water group channel) downcomer region) b e b e b e b e b e b e ϕ f (0.1-10 MeV) 12.1 7.6 1.0?2.6 1.4?2.1 0.13 0.16 1.3 1.5 0.83 1.0 0,012 0,011 ϕ at (1 eV – 100 5.8 3.7 1.1?2.4 1.3?1.9 0.11 0.13 1.2 1.4 0.76 0.89 0,036 0,037 keV) ϕ t (less than 1 3.8 2.6 7.0?9.6 6.0?6.5 1.8 2.3 4.6 5.4 2.8 2.9 1,28 1,38 eV)
VI. Evaluation of technical and economic characteristics of NEDC Sensitivity analysis for technical and economic characteristics of NEDC on RUTA-70 were carried out using DEEP-3 For coupling to MED: variables “ maximum brine temperature ” and site specific parameter “ required water plant capacity ” Objects of analysis: “ maximal achievable water plant capacity ” and “ product water cost ”
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